ML080930284

Exam 05000269, 270, & 287/2008301 Final RO Written Exam & References

ML080930284
Person / Time
Site:	Oconee
Issue date:	03/20/2008
From:	NRC/RGN-II
To:	Duke Energy Carolinas
References
50-269/08-301, 50-270/08-301, 50-287/08-301
Download: ML080930284 (77)

Text

Final Submittal (Blue Paper)

OCD~ zC(J8 -3:>1 ~E E~{A~rjD~

3/Z<J/z< 100 B. ONE Main FDW pump and control pzr level> 180 C. BOTH Main FDW pumps and control pzr level> 100 D. BOTH Main FDW pumps and control pzr level> 180

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 2 Unit 1 plant conditions:

Reactor power = 1000/0 pzr code safety valve is suspected of having steam blowing past its seat.

pzr temperature = 648 of Quench tank pressure =5 psig Based on plant conditions, which ONE of the following describes the expected temperature downstream of the pzr code safety valve and why?

A. 228 of Because leakage past a valve is a constant enthalpy process B. 162 of Because leakage past a valve is a constant enthalpy process C. 228 of Because leakage past a valve is a constant entropy process D.1620F Because leakage past a valve is a constant entropy process

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 3 Unit 1 plant conditions:

Time = 1700 Reactor power = 100%

Time = 1701 Reactor tripped due to a SBLOCA Time = 1706 RCS pressure =425 psig slowly decreasing All SCMs =OaF and stable HPI header A flow = 478 gpm and stable 1A and 1B HPI pumps operating 1C HPI pump breaker failed open Based on the above conditions, which ONE of the following describes what valve must be opened and what flow limit is in effect in accordance with Rule 2 (Loss of SCM)?

A. Open 1HP-409 and ensure total HPI flow is :5 950 gpm B. Open 1HP-409 and ensure total HPI flow is :5 750 gpm C. Open 1HP-41 0 and ensure total HPI flow is :5 950 gpm D. Open 1HP-41 0 and ensure total HPI flow is :5 750 gpm

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 4 Which ONE of the following describes the maximum RB pressure (psig) that will allow securing the RBS system and why it should be secured within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the event in accordance with the EOP LOCA CD tab?

A. <3 Minimize boric acid corrosion of electrical components in containment B. < 3 Minimize the amount of water recirculating outside of containment to reduce dose to the public C. < 10 Minimize boric acid corrosion of electrical components in containment D. < 10 Minimize the amount of water recirculating outside of containment to reduce dose to the public

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 5 Unit 2 plant conditions:

Reactor power = 200/0 and stable Statalarms actuated:

y 2SA-9/D2 (RCP VIBRATION HIGH) actuated y

2SA-16/D2 (RC Pump Motor 2B1 Oil Pot Low Level) actuated All RCPs seal leakage flow = 0 gpm 2B1 RCP parameters:

SEAL RETURN FLOW =4.0 gpm HIGHEST VIBRATIONS y

Motor shaft =3.2 mils y

Spool piece = 17.6 mils y

Upper bearing = 17.3 mils SEAL RETURN TEMPERATURE =186°F increasing OIL POTS y

Upper - Level =+.22 11 steady and Temperature = 108°F steady y

Lower - Level =-1.3" decreasing and Temperature = 113°F increasing MOTOR BEARING TEMPERATURE y

Upper Guide = 130°F decreasing y

Lower Guide =205°F increasing y

Thrust = 140°F steady Based on the above conditions, which ONE of the following describes why the 2B1 RCP should be tripped immediately?

A. High seal return flow B. High sustained vibratio'n C. Seal return temperature increasing D. Motor lower guide bearing temperature increasing

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 6 Unit 1 initial conditions:

Reactor power = 100%

Current conditions:

1HP-120 (RC VOLUME CONTROL) air line is severed Based on the above conditions, which ONE of the following describes the initial pzr level change and the valve that will be used to control pzr level?

A. increase / 1HP-26 B. increase / 1HP-41 0 C. decrease / 1HP-26 D. decrease / 1HP-41 0

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 7 Unit 1 plant conditions:

A load rejection caused an RCS Pressure spike Pressurizer spray valve failed to fully reseat RCS pressure = 2145 psig decreasing slowly Based on the above conditions, which ONE of the following lists ALL of the banks of Pressurizer Heaters that are energized?

A. Bank 1 and 2 ONLY B. Banks 1 and 3 ONLY C. Banks 1,2 and 3 ONLY D. Banks 1,2,3 and 4

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 8 Unit 1 initial conditions:

Reactor power = 78%

1A SG has a 56 gpm tube leak Unit shutdown in progress Current conditions:

Reactor power = 4%

decreasing TBVs have failed closed 1A SG level = 36 inches SUR increasing slowly 1B SG level = 23 inches SUR increasing slowly An NEO is using the ADVs to control Turbine Header Pressure at 885 psig Subsequently, the reactor is manually tripped as directed by procedure.

Which ONE of the following describes the required action of the NEO at the ADVs immediately following the reactor trip and why?

A. 1B ADV must be throttled in the closed direction to increase 1B SG level B. Both ADVs must be throttled in the closed direction to stabilize MS pressure C. 1A ADV must be throttled in the open direction to prevent 1A SG overfill D. Both ADVs must be throttled in the open direction to prevent lifting the MSRVs

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 9 Unit 1 plant conditions:

Time = 10:00:00 Reactor power = 100%

1A MD EFDW pump OOS 1SA2/A9 (MS PRESS HIGH/LOW) alarms Time = 10:00:20 1A SG pressure = 905 psig decreasing 1B SG pressure = 62 psig decreasing RB pressure = 3.6 psig increasing Core SCM has decreased to 3QF and is now increasing Based on the above conditions, which ONE of the following describes level (XSUR) at which 1A SG will be controlled 30 minutes from now?

1A SG will be controlled...

A. automatically at 30".

B. automatically at 240".

C. manually at 60".

D. manually at 270".

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 10 Unit 1 plant conditions:

Time = 0200 Power = 100%

Time = 0202 11 AI SG pressure = 100 psig 11 BI SG pressure =810 psig RB pressure = 3.6 psig PZR level =9 inches decreasing RCS pressure = 1610 psig decreasing CETCs = 520°F and decreasing.

Based on the above conditions, which ONE of the following is correct?

A has occurred and ASSUME NO OPERATOR ACTION A. Small break LOCA / ES Channels 3 and 4 have actuated B. Small break LOCA / ES Channels 3 and 4 have NOT actuated C. Main FDW line break / AFIS will have actuated to secure the Main FDW pumps D. Main FDW line break / AFIS will NOT have actuated to secure the Main FDW pumps

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 11 Unit 1 plant conditions:

Blackout tab in progress Which ONE of the following describes the maximum allowed time (minutes) to establish SSF RCMU flow and the bases for this limit?

A. 14 / prevents RCP seal failures B. 14 / ensures minimum makeup required for cooldown C. 20 / prevents RCP seal failures D. 20 / ensures minimum makeup required for cooldown

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 12 Plant initial conditions:

Units 1 and 2 Reactor power = 100%

Units 3 Reactor power = 26%

Switchyard Isolation occurs Unit 1 regains power from CT-1 CT-2 Lockout has occurred Current conditions:

Unit 2 SSF is activated Unit 2 SSF RCMU pump operating Unit 2 1s PORV has seat leakage Based on the above conditions, which ONE of the following describes who in accordance with OMP 2-1 (Duties and Responsibilities of On-Shift Operations Personnel) is designated to activate the SSF and where the PORV block valve can be operated to stop the leakage?

A. Unit 2 1s BOP / SSF control room ONLY B. Unit 3 1s BOP / SSF control room ONLY C. Unit 2 1s BOP / SSF AND Plant control room D. Unit 3 1s BOP / SSF AND Plant control room

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 13 Unit 1 initial conditions:

Reactor power = 100%

Current conditions:

1A SG XSUR Primary =Blank 1A SG XSUR Backup = 152 11 stable 1B SG XSUR Primary = 152 11 stable 1B SG XSUR Backup = Blank 1A SG outlet Pressure (Dixon) Train A =895 psig 1B SG outlet Pressure (Dixon) Train A =895 psig 1A SG outlet Pressure (Dixon) Train B = Blank 1B SG outlet Pressure (Dixon) Train B = Blank Based on current conditions, which ONE of the following states the power supply that has de-energized?

A. 1DCA B. 1KVIB C. 1KVIC D. 1DCB

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 14 Unit 1 initial conditions:

Reactor power = 100 1SA6/B2 INVERTER 1DID SYSTEM TROUBLE actuated Current conditions:

NEO reports:

1SA13/A81NVERTER 1010 INPUT VOLTAGE LOW actuated Inverter 1DID output voltage low Based on the above conditions, which ONE of the following describes the alarm setpoint (volts DC) and what action does 1SA131A8 ARG direct if the inverter output voltage remains low?

A. 110 1 Transfer DC bus 1DID power to alternate unit (Unit 2 DCB)

B. 110 1 Transfer power for 1KVID to Regulated Power Panel Board (1 KRA)

C. 121 1 Transfer DC bus 1DID power to alternate unit (Unit 2 DeB)

D. 121 1 Transfer power for 1KVID to Regulated Power Panel Board (1 KRA)

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 15 Unit 1 initial conditions:

Reactor power = 100%

Current conditions:

A, Band C LPSW pumps tripped AP/24, Loss of LPSW in progress RCP temperatures increasing Based on the above conditions, which ONE of the following statements is a required action per AP/24?

A. If a RCP radial bearing temperature exceeds 225 QF, manually trip the Reactor and stop ONLY that RCP B. If a RCP radial bearing temperature exceeds 225 QF, manually trip the Reactor and stop ALL RCPs C. If a RCP motor stator temperature exceeds 260 QF, manually trip the Reactor and stop ONLY that RCP D. If a RCP motor stator temperature exceeds 260 QF, manually trip the Reactor and stop ALL RCPs

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 16 Unit 2 initial conditions:

AP/2/A/1700/022, Loss of Instrument Air in progress Current conditions:

Instrument Air Pressure = 92 psig decreasing slowly An operator has been dispatched to IIPlace all Backup IA Compressor control switches in BASEII Which ONE of the following describes how this step should be performed and why?

When transferring from STBY to BASE the switch should...

A. remain in OFF for at least 3 seconds to prevent activating the anti-pump circuit.

B. remain in OFF for at least 3 seconds to prevent tripping the breaker.

C. be turned as quickly as possible to prevent tripping the breaker.

D. be turned as quickly as possible to prevent activating the anti-pump circuit.

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 17 Unit 1 initial conditions:

Reactor power = 100%

TD EFDWP OOS Current conditions:

Reactor power = 40%

decreasing "1 A" Main Steam Line Pressure =950 psig and slowly decreasing "1 B" Main Steam Line Pressure = 105 psig and decreasing BOTH Main FDW pumps tripped BOTH MDEFDW pumps tripped RCS Temperature =505°F and decreasing SCM = 7°F decreasing slowly OATC is performing Immediate Manual Actions (IMAs)

BOP is performing a Symptoms Check Based on the above conditions, which ONE of the following is correct?

The OATC will and the BOP operator will perform A. complete IMAs / Rule 1 (ATWS/Unanticipated Nuclear Power Production)

B. perform Rule 1 (ATWS/Unanticipated Nuclear Power Production) / Rule 2 (Loss of SCM)

C. perform Rule 1 (ATWS/Unanticipated Nuclear Power Production) / Rule 3 (Loss of Main or Emergency FDW)

D. complete IMAs / Rule 5 (Main Steam Line Break)

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 18 Unit 1 initial conditions:

Reactor power = 35%

stable AP/34 (Degraded Grid) in progress Current conditions:

Generator voltage cannot be maintained within the capability curve Based on current conditions, which ONE of the following describes a required action in accordance with AP/34?

A. Open PCB 20 and 21 B. Manually trip ALL operating Keowee Units C. Initiate AP/29 (Rapid Unit Shutdown)

D. Manually trip the Turbine

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 19 Unit 1 plant conditions:

Reactor power = 50%

Power escalation in progress Control rods failed to stop moving out when the CTPD Set was reached The OATC took ICS to manual Rod motion has stopped Tave = 582QF increasing Based on the above conditions, which ONE of the following is required in accordance with plant transient response process contained in SOMP 1-02 (Reactivity Management)?

A. Increase FDW to restore Tave to setpoint B. Increase FDW to restore heat balance and stop the RCS pressure transient C. Insert rods to restore Tave to setpoint D. Insert rods to restore heat balance and stop the RCS pressure transient

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 20 Unit 1 initial conditions:

Reactor power = 100%

Turbine trips Current conditions:

Reactor power = 140/0 decreasing ALL HPI Pumps operating 1A HPI header flow = 675gpm 1B HPI header flow = 375gpm HPI seal injection flow = 38gpm 1HP-24 OPEN 1HP-25 indicating lights not LIT 1HP-26 and 27 OPEN Based on the above conditions, which ONE of the following describes the actions (if any) required to place the HPI system in the proper configuration?

A. No actions are required B. Stop 1A or 1B HPI pump C. Throttle 1HP-26 to reduce 1A HPI header flow < 475gpm D. Ensure total HPI injection flow including RCP Seal Injection is < 950 gpm

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 21 Unit 1 initial conditions:

Reactor power = 100%

Current conditions:

Condenser vacuum = 5.6 inches Hg stable Based on the above conditions, which ONE of the following describes the expected SGs pressure (psig) and on what PAM instrument can it be monitored?

ASSUME NO OPERATOR ACTIONS A. Less than 1020 / 1A and 1B MS PRESS B. Less than 1020 / 1A and 1B SG OUT PRESS C. Greater than 1020 / 1A and 1B MS PRESS D. Greater than 1020 / 1A and 1B SG OUT PRESS

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 22 Unit 1 plant conditions:

Unit shutdown in progress Reactor power = 80%

decreasing SGTL 1A SG =20 gpm Based on the above conditions, which ONE of the following describes the most significant radiation hazard in the vicinity of the Main Steam lines and actions taken to limit the spread of contamination to other units?

A. 6.7 Mev y's from the decay of N16 All 3 units Auxiliary Steam Systems are aligned such that each unit is supplying its own Auxiliary Steam Loads.

B. 6.7 Mev y's from the decay of N16 The Turbine Building Sump Trenches are split to prevent secondary system leaks from the affected Unit from going to the other units.

C. 2.2 Mev y's from the decay of C060 due to the primary to secondary leakage All 3 units Auxiliary Steam Systems are aligned such that each unit is supplying its own Auxiliary Steam Loads.

D. 2.2 Mev y's from the decay of C060 due to the primary to secondary leakage The Turbine Building Sump Trenches are split to prevent secondary system leaks from the affected Unit from going to the other units.

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 23 Unit 1 plant conditions:

Reactor power = 100%

1SA-08/A9 RM AREA MONITOR RADIATION HIGH, has actuated 1RIA-39 (CNTL RM GAS) is in alarm HIGH Based on the conditions above, which ONE of the following describes the actions directed to be performed and the reason for the actions?

A. Start BOTH Outside Air Booster Fans and open Control Room doors to provide dilution to the air in the Control Room and reduce airborne radiation levels B. Start BOTH Outside Air Booster Fans and the dampers align to ensure Control Room pressure is positive in relation to outside atmosphere C. Start ONE Outside Air Booster Fan and open Control Room doors to provide dilution to the air in the Control Room and reduce airborne radiation levels D. Start ONE Outside Air Booster Fan and the dampers align to ensure Control Room pressure is positive in relation to outside atmosphere

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 24 Plant conditions:

A dropped rod caused a runback from 100 to 55%

power The operating crew has notified Chemistry that power changed greater than 15%

in one hour Which one of the following identifies the analysis to be run by Chemistry and the reason for it?

A. E Bar to re-calculate the RCS gross activity limit B. Dose Equivalent Iodine to monitor for fuel failures and TS compliance C. RCS Boron concentration to verify proper shutdown margin D. Gamma Isotopic Analysis to determine if a crud burst requires RCS cleanup actions

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 25 Unit 1 initial plant conditions:

Reactor power = 25%

1FDW-41 (1 B Main FDW Control) in MANUAL Current conditions:

ICS HAND power lost Based on the above conditions, which ONE of the following describes the affect on SG feed flow assuming no operator action and what would happen if the AUTO pushbutton is depressed on the 1FDW-41 Hand/Auto Station?

A. 1B SG overfeed will occur and 1FDW-41 will transfer to AUTO.

B. 1B SG overfeed will occur and 1FDW-41 will remain in MANUAL.

C. 1B SG underfeed will occur and 1FDW-41 will transfer to AUTO.

D. 1B SG underfeed will occur and 1FDW-41 will remain in MANUAL.

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 26 Unit 1 initial conditions:

Reactor power = 100%

HWP Pump Load Shed Defeat Switch selected to 1B Both Channels of CRD trip confirm circuitry inoperable Current conditions:

Turbine trips ES Channels 1 and 2 actuates Based on the above conditions, which ONE of the following describes which HWP(s) will be operating and the purpose of the LOCA Load Shed Logic circuit?

ASSUME NO OPERATOR ACTIONS A. ONLY the 1B HWP will be operating LOCA Load Shed prevents overloading CT-4 or CT-5 B. ALL three HWPs will be operating LOCA Load Shed prevents overloading CT-4 or CT-5 C. ONLY the 1B HWP will be operating LOCA Load Shed reduces the post LOCA voltage dip on ES buses D. ALL three HWPs will be operating LOCA Load Shed reduces the post LOCA voltage dip on ES buses

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 27 Unit plant conditions:

LOCA CD tab in progress ALL SCMs =4 QF increasing RCS pressure is controllable Statalarm 1SA7/E2 (LP Injection ES Bypass Permit) actuated Which ONE of the following describes when Statalarm 1SA7/E2 actuates and the required action in accordance with the LOCA CD tab?

A. RCS Pressure = 900 psig Bypass ES Channels 1 and 2 B. RCS Pressure =900 psig Bypass ES Channels 3 and 4 C. RCS Pressure = 1750 psig Bypass ES Channels 1 and 2 D. RCS Pressure = 1750 psig Bypass ES Channels 3 and 4

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 28 Unit 1 plant conditions:

Unit Startup is in progress RCS Pressure =800 psig 1A1 and 1A2 RCPs are operating Based on the above conditions, which ONE of the following would prevent 1B2 RCP from starting?

A. RCS temperature =300°F B. Oil lift pressure = 660 psig C. HPI Seal Injection flow rate =24 gpm D. Total Component Cooling flow =550 gpm

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 29 Unit 1 plant conditions:

BWST Temperature =85°F LOST Temperature = 105°F RCS pressure =685 psig Based on the above conditions, which ONE of the following describes acceptable suction source(s) for Auxiliary Pressurizer Spray and the reason for the applicable limit in accordance with SLC 16.5.8 (Pressurizer)?

A. LOST ONLY / to reduce thermal stress on the pzr spray nozzle B. LOST or the BWST / to reduce thermal stress on the pzr spray nozzle C. LOST ONLY / to reduce potential for exceeding pzr heater capacity O. LOST or the BWST / to reduce potential for exceeding pzr heater capacity

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 30 Unit 1 plant conditions:

RCS pressure = 290 psig RCS temperature = 240QF 1A1 and 1A2 RCP operating 1LP-11 (1A LPI COOLER INLET) failed closed Which ONE of the following describes the LPI mode that will be used for unit cooldown based on the failure of 1LP-11 and what actions, if any, are required to continue the cooldown per OP/1/A/11 02/01 0 (Controlling Procedure For Unit Shutdown)?

A. Series Mode 1 no additional action is required B. Series Mode 1 110 RCP operation must be established C. Switchover Mode 1 no additional action is required D. Switchover Mode 1 1/0 RCP operation must be established

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 31 Unit 1 plant conditions:

Mode 5 with RCS temperature at 170 of with LPI maintaining temperature The operating crew is preparing to makeup to the RCS No RCPs are operating RCS Boron Concentration = 1500 PPM COLR Boron Concentration limits are:

~

Refueling - 2200 PPM

~

1% ilK/K @ 70 of - 1400 PPM

~

1% ilK/K @ 200 of - 1225 PPM Based on the above conditions, which ONE of the following is the minimum boron concentration (PPM) allowed for the makeup source?

A. 2201 B. 1501 C. 1401 D. 1226

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 32 Unit 1 initial conditions:

LBLOCA

• .1 (ES Actuation) in progress RCS pressure = 50 psig decreasing 1A and 1B LPIPs operating Current conditions:

1A LPIP trips Based on the above conditions, which ONE of the following describes actions to be taken in accordance with Enclosure 5.1 AND the results of that action?

A. Close 1LP-17, LPI Flow will be aligned to ONLY the B Injection Nozzle B. Close 1LP-12, LPI Flow will be aligned to ONLY the B Injection Nozzle C. Close 1LP-17, LPI Flow will be aligned to BOTH Injection Nozzles D. Close 1LP-12, LPI Flow will be aligned to BOTH Injection Nozzles

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 33 Unit 1 plant conditions:

Time = 0400 Reactor Power =100 Time = 0405 RCS pressure =1500 psig decreasing RB pressure = 9 psig Time =0415 RCS pressure =1100 psig decreasing RB pressure = 11 psig

• .1 (ES Actuation) actions completed awaiting SRO direction to exit Time = 0500 RCS pressure =180 psig decreasing RB pressure = 7 psig Based on the above conditions, which ONE of the following actions is directed to be taken immediately in accordance with Enclosure 5.1?

A. Close 1CF-1 and 1CF-2 B. Start ALL LPI Pumps C. Secure BOTH RBS Pumps D. Start ONLY A & B LPI Pumps

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 34 Unit 1 was operating at 100 power when the following trends were observed:

RCS pressure began to lower Quench tank level began to rise Quench tank pressure began to rise Which ONE of the following correctly describes the INITIAL effect on containment when these trends are observed?

A. Containment pressure rises. 1RIA-47 indicates an increase in radiation level B. Containment pressure rises. 1RIA-47 indicated radiation level remains constant.

C. Containment pressure remains constant. 1RIA-47 indicates an increase in radiation level D.

Containment pressure remains constant. 1RIA-47 indicated radiation level remains constant

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 35 Unit 1 initial conditions:

Reactor power = 100%

Switchyard isolation occurs Current conditions:

Reactor trip CT1 lockout Based on the above conditions, which ONE of the following states how long after the reactor trip the CC pumps will re-energize and from what source will they be powered?

A. 21 seconds / 1XL and 1XN B. 21 seconds / 1XO and 1XP

c. 31 seconds / 1XL and 1XN D. 31 seconds / 1XO and 1XP

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 36 Unit 1 initial conditions:

Reactor power = 100%

Current conditions:

BOTH CC pumps have TRIPPED RCP seal injection = 8 gpm/pump Based on current conditions, which ONE of the following describes the continued operation of the RCPs?

A. RCPs must be secured immediately B. RCPs must be secured within 30 minutes C. RCPs may continue operation indefinitely D. RCP can operate up to 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 37 Unit 1 initial conditions:

Reactor power = 100%

A transient occurs Current conditions:

RCS pressure = 2130 psig decreasing pzr level = 78 inches stable pzr temperature =639 QF decreasing Based on the current conditions, which ONE of the following states the status of the pzr heaters and why?

A. All pzr heaters are OFF to protect the heaters due to low pzr level B. ALL pzr heater would be energized to increase RCS pressure to normal C. Bank 1, 2, and 3 pzr heaters ONLY will be energized to increase ReS pressure D. Bank 2 pzr heaters will be energized by the Saturation Recovery Circuit to establish saturated conditions in the pzr

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 38 Unit 1 initial conditions:

Reactor power = 100%

Current conditions:

1B1 Reactor coolant pump trips Based on the above conditions, which ONE of the following RPS trips will prevent exceeding the DNBR safety limit?

A. High flux B. FluX/Pump C. Flux/Flow/Imbalance D. High RCS Temperature

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 39 Unit 1 initial conditions:

Reactor power = 100%

Current conditions:

Reactor trip due to Variable Low Pressure Which ONE of the following sets of detector failures resulted in the above reactor trip?

ASSUME NO OPERATOR ACTION A. WR RCS pressure A and B fail low B. WR RCS Pressure A and, B fail high C. NR RCS pressure A and E fail low D. NR RCS Pressure A and E fail high

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 40 Unit 1 plant conditions:

A SBLOCA has occurred EOP LOSCM tab in progress Reactor Building pressure = 25 psig decreasing EOP Enclosure 5.12 (ECCS Suction Swap to RBES) in progress y

RBES has just been aligned to the suction of the LPI Pumps Based on the above conditions, which ONE of the following describes the initial BWST level response and the required condition(s) for isolating LPI pumps from the BWST?

A. BWST level initially decreases When BWST level is 9 feet and RB level is increasing.

B. BWST level initially decreases When BWST level is less than 6 feet C. BWST level initially remains constant When BWST level is 9 feet and RB level is increasing.

D. BWST level initially remains constant When BWST level is less than 6 feet

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 41 Unit 1 plant conditions:

Reactor power = 100%

RBNS Level is increasing LPSW RBCU COOLER Flows are as follows:

~

1A INLET =990 gpm

~

1A OUTLET = 580 gpm

~

1C INLET =930 gpm

~

1C OUTLET = 970 gpm Based on the conditions above, which ONE of the following describes the condition of the RBC Units, AND the action directed to correct the condition?

A. The RBCU "G" is leaking, Isolate the "G" RBCU outlet, then inlet to prevent water hammer and minimize generation and processing of liquid radwaste.

B. The RBCU "A" is leaking, Isolate the A RBGU outlet, then inlet to prevent water hammer and minimize generation and processing of liquid radwaste.

G. The RBGU "G" is leaking, Isolate the "C" RBCU inlet, then outlet to maintain containment integrity and prevent dilution of the RB Sump.

D. The RBGU "A" is leaking, Isolate the "A" RBCU inlet, then outlet to maintain containment integrity and prevent dilution of the RB Sump.

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 42 Unit 1 initial conditions:

Time =0400 Reactor power =20%

Current conditions:

Time =0401 RB pressure = 14 psig increasing 1TO de-energized Based on the above conditions, which ONE of the following describes the expected status of the Reactor Building Spray System (RBS)?

A. 1A RBS pump - OPERATING 1B RBS pump - OFF 1BS OPEN 1BS OPEN B. 1A RBS pump - OPERATING 1B RBS pump - OFF 1BS OPEN 1BS CLOSED C. 1A RBS pump - OFF 1B RBS pump - OPERATING 1BS OPEN 1BS OPEN D. 1A RBS pump - OFF 1B RBS pump - OPERATING 1BS CLOSED 1BS OPEN

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 43 Unit 1 initial conditions:

Reactor power = 100%

Troubleshooting in progress on Channel IIAII Reactor Building Spray Pressure String Current conditions:

The High RB pressure Contact Buffer is removed in ChannelllA" 1SA-7/D3 (ES RB Spray Pwr Supply Failure or Channel "A" Module Removed) actuated Based on the above conditions, which ONE of the following describes the impact on the ES channels?

A. ES Channel 7 and 8 are in a 1 out of 2 trip logic Mode B. ES Channel 7 and 8 are in a 2 out of 2 trip logic Mode C. ES Channel 5 and 6 are in a 1 out of 2 trip logic Mode D. ES Channel 5 and 6 are in a 2 out of 2 trip logic Mode

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 44 Unit 3 plant conditions:

Critical just below the Point of Adding Heat The Turbine Bypass Valves are in MANUAL at the Auxiliary Shutdown Panel (ASDP)

Turbine Header Pressure = 885 psig Based on the above conditions, which ONE of the following describes initial turbine header pressure response if a manual reactor trip is initiated?

Turbine Header Pressure will...

A. decrease and RCS temperature will decrease until TBVs are closed.

B. increase to approximately 1010 psig and RCS temperature will increase to 555°F.

C. remain at approximately 885 psig and RCS temperature will remain relatively constant.

D. increase to the main steam relief valve settings and RCS temperature will be maintained at approximately 560°F.

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 45 Unit 1 initial conditions:

Reactor power = 100%

ICS is in MANUAL Current conditions:

AP/29 (Rapid Unit Shutdown) is initiated to reduce power to 15%

Based on the above conditions and in accordance with AP/29, which ONE of the following describes which Main FDW pump will be secured first and what plant indications will be, used to determine when the pump will be removed from service?

A. 1A Main FDW pump I when a statalarm for FDWP flow at or below minimum is received for the associated Main FDW pump and CTP < 65%

B. 1A Main FDW pump I =325 MWe C. 1B Main FDW pump I when a statalarm for FDWP flow at or below minimum is received for the associated Main FDW pump and CTP < 65%

D. 1B Main FDW pump I = 325 MWe

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 46 Unit 1 initial conditions:

Time = 0400 Reactor power = 100%

TDEFDW Pump OOS Switchyard Isolation occurs Current conditions:

Time = 0403 1A and 1B MDEFDW Pump operating Power has been lost to the HAND/AUTO Station for 1FDW-316 Based on the above conditions, which ONE of the following describes the response of "1 B" SG level?

ASSUME NO OPERATOR ACTION A. Steadily lower to "dryout" B. Maintain at 30" C. Maintain at 240" D. Steadily rise and overflow to the steam lines

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 47 Unit 2 initial conditions:

Reactor power = 27%

PCB-24 (Unit 2 Generator Output Breaker-to Yellow Bus) is OPEN Current conditions:

Reactor trip Based on the above conditions, which ONE of the following describes the MFB breaker operation and the RCP status?

The IINII breakers will open and the....

A.

II Ell breakers will NOT close automatically RCPs will trip B. IIEII breakers will close in 1.7 seconds RCPs will remain in operation C. IIEII breakers will close immediately RCPs will remain in operation D. IIEII breakers will close in 21 seconds RCPs will trip

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 48 Which ONE of the following is powered from DCA (125VDC Control Power Bus)?

A. EFWPT Auxiliary Oil Pump B. KSF1 Inverter C. Main FDW Pump Turbine Control power D. KX Inverter

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 49 Unit 1 initial conditions:

Reactor power = 100%

ACB-3 closed 230 KV Switchyard Voltage sustained at 223.1 KV Current conditions:

RCS pressure = 1120 psig RB pressure = 3.9 psig Based on the above conditions, which ONE of the following describes the source of power and the transformer which will energize the Unit 1 Main Feeder Busses?

ASSUME NO OPERATOR ACTIONS A. ONS Switchyard via CT-1 Transformer B. Keowee Unit 1 via CT-4 Transformer C. Keowee Unit 2 via CT-1 Transformer D. Keowee Unit 2 via CT-4 Transformer

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 50 Which ONE of the following will DIRECTLY initiate an emergency start signal to BOTH Keowee Units?

A. STARA relay actuation B. Switchyard Isolation Confirm signal C. Standby Breaker Close Initiation signal D. Keowee Emergency Start ChannelllBII is manually actuated from Unit 2 1s Cable Room.

OCONEE NRC RO EXAM 03-20-200S 1 POINT Question 51 Unit 1 initial conditions:

Reactor power = 100%

1A GWD tank release in progress 1RIA-3S OOS Current conditions:

Loss of power to RM-80 skid of 1RIA-37 1SAS/B9 RM PROCESS MONITOR RADIATION HIGH in alarm 1SAS/B1 0 RM PROCESS MONITOR FAULT in alarm Based on the above conditions, which ONE of the following states the status of 1GWD-4 (A GWD TANK DISCHARGE) and stipulations for the release?

A. 1GWD-4 will remain open I GWD tank release may continue if 1RIA-37 is re-energized within one hour.

B. 1GWD-4 will automatically close I GWD tank release may be re-initiated as long as 1RIA-37 is re-energized within one hour.

C. 1GWD-4 will remain open I GWD tank release may continue as long as two independent samples are obtained.

D. 1GWD-4 will automatically close I GWD tank release may be re-initiated as long as two independent samples are obtained prior to the release.

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 52 Unit 1 initial conditions Mode 5 RB Purge in operation Current conditions:

Radiation levels in the RB increasing Based on current conditions, which ONE of the following describes the operation of the Unit Vent Radiation Monitors 1RIA-45 and 1RIA-46 when the switchover acceptance range setpoint is reached?

1RIA-45 will read and 1RIA-46 will provide A. offscale high

/ only alarm and unit vent radiation level indication.

B. offscale high / the same interlock functions that RIA-45 performs.

C. ZERO / only alarm and unit vent radiation level indication.

D. ZERO / the same interlock functions that RIA-45 performs.

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 53 Unit 1 and 2 initial conditions:

A & B LPSW pump operating Current conditions:

1SA9/A9 LPSW HEADER A PRESS LOW A LPSW pump amps = 15 - 35 fluctuating B LPSW pump amps = 55 stable LPSW HDR PRESS = rapidly fluctuating between 60 & 75 psig Based on current conditions, which ONE of the following describes the status of the LPSW pumps and what actions are directed by plant procedures?

A. The A LPSW pump is cavitating 1 Place the Unit 1/2 STANDBY LPSW PUMP AUTO START CIRCUIT in DISABLE then stop LPSW Pump A and start LPSW Pump C B. The A LPSW pump has a sheared shaft 1 Place the Unit 112 STANDBY LPSW PUMP AUTO START CIRCUIT in DISABLE then stop LPSW Pump A and start LPSW Pump C C. The A LPSW pump is cavitating 1 Start LPSW Pump C then stop LPSW Pump A D. The A LPSW pump has a sheared shaft 1 Start LPSW Pump C then stop LPSW Pump A

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 54 Unit 1 initial conditions:

Reactor power = 1000/0 Power reduction to 700/0 initiated to secure RCP STANDBY 1 Backup IA Compressor start IA pressure = 91 psig decreasing AP/22 (Loss of Instrument Air) initiated Current conditions:

IA pressure = 85 psig stable Reactor power = 80%

decreasing Total FDW flow =9.9 E6 Ibm/hr stable Based on current conditions, which ONE of the following describes the actions directed by AP/22?

A. Trip the reactor and BOTH MFWPs B. Dispatch operator to Manually OPEN 1CC-8 C. Dispatch operator to throttle 1HP-31 to ~ 32 gpm D. Isolate the LPSW supply to the RB Aux Coolers

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 55 Unit 1 initial conditions:

LOCA RB Pressure = 4.5 psig increasing RCS Pressure = 1500 psig decreasing Current conditions:

RB Pressure =2.5 psig stable RCS Pressure = 1800 psig stable ES reset is desired Based on the current conditions, which ONE of the following describes the components that must be reset in order to allow the HPIPs ES Logic to be reset?

A. HPI Trip Bistables in Analog Channels AlBIC I Reset ES Ch 1&2 Digital Channels B. HPI and RB Pressure Trip Bistables in Analog Channels AlBIC I Reset ES Ch 1&2 Digital Channels C. HPI Trip Bistables in Analog Channels AlBIC I Reset ES Ch 3&4 Digital Channels D. HPI and RB Pressure Trip Bistables in Analog Channels AlBIC I Reset ES Ch 3&4 Digital Channels

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 56 Unit 1 initial conditions:

Time 0900 Reactor power = 68%

CR group 2 rod 3 dropped into the core 1B2 RCP secured 1SA4/C1 QUADRANT POWER TILT in alarm Current conditions Time 1300 Encl 4.15 (Recovery of Dropped/Misaligned Safety or Regulating Control Rod With Diamond In automatic) of OP/1/A/11 05/019 (Control Rod Drive System) in progress.

Reactor Engineering has determined no maneuvering limitations other than those specified by the procedure need to be applied Based on above conditions, which ONE of the following states the maximum reactor power allowed by Tech Spec and during the recovery of the dropped control rod, what procedural limitations are required for the rate of control rod withdrawal?

A. 60%

/ Withdrawn with no designated wait periods B. 450/0 / Withdrawn with no designated wait periods C. 60%

/ Withdrawn in 10% increments spaced 30 min apart D. 45%

/ Withdrawn in 10% increments spaced 30 min apart

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 57 Unit 1 Conditions 0800 Reactor power = 100%

stable pzr level =210" decreasing RC MAKE UP FLOW = 120 gpm increasing 1RC-66 Relief Outlet Temp = 118QF increasing slowly Quench Tank level = 86 inches stable AP/2 (RCS Leakage) initiated 0810 RC MAKE UP FLOW = 160 gpm increasing pzr level = 190" decreasing In accordance with AP-2, which ONE of the responses below answers the following?

a) What is the required action for conditions at 0800?

b) What is the required action for conditions at 081 O?

A. Close 1RC-4 / Initiate rapid unit shutdown B. Close 1RC-4 / Trip the reactor C. Close 1HP-5 / Initiate rapid unit shutdown D. Close 1HP-5 / Trip the reactor

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 58 Unit 1 plant conditions:

Reactor power = 100%

1HP-120 (RC Volume Control) has failed CLOSED due to controller malfunction 1HP-5 (Letdown Isolation) is CLOSED PZR level = 21 0 inches Total HPI Nozzle Warming line flow =8 gpm Based on the above conditions, which ONE of the following will be PZR Level (inches) in one hour?

Assume:

No additional operator actions ReS Temperature remains constant No thermal expansion of the water used for makeup A.275 B. 295 C. 310 D.330

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 59 Unit 1 initial conditions:

Time =0400 Reactor power = 100%

Current conditions:

Time = 0401 Control Rods are Inserting Neutron Error is Negative Feedwater flow is Increasing SG levels are increasing RPS Channel A trip Based on the current conditions, which ONE of the following malfunctions has occurred?

A. Controlling NI signal has failed HIGH B. Controlling RCS NR pressure failed LOW C. Controlling Turbine Header Pressure failed HIGH D. Controlling Tave failed LOW

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 60 As indicated on the ICCM plasma display, which ONE of the following describes the lowest indicated CETC temperature (OF) at which core uncovery is certain AND the indicated CETC temperature when fuel melt is occurring?

A. 1200 / 5000 B. 1200/2500 C. 2200/5000 D. 2200 / 2500

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 61 Which ONE of the following describes who determines that a RB Continuous Release is allowed and after it is started what are the requirements for sampling the RB atmosphere in accordance with OP/11 02/014 (RB Purge System)?

A. Shift RP 1 Release may continue indefinitely after initial 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> without submitting daily sample requests.

B. Shift RP 1 Release may continue indefinitely provided RP assigns a new GWR number and sample results are entered in the Unit Log every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

C. CRSRO 1 Releases may continue indefinitely after initial 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> without submitting daily sample requests.

D. CRSRO 1 Release may continue indefinitely provided RP assigns a new GWR number and sample results are entered in the Unit Log every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 62 Unit 1 plant conditions:

Reactor power = 18%

decreasing 1SA2/E8, MS STM GEN "A" LEVEL LOW LIMIT in alarm 1SA2/E9, MS STM GEN "B" LEVEL LOW LIMIT in alarm 1A SG level = 25" SUR stable 1B SG level = 25" SUR stable 1A SG Loop Tave =580 of slowly decreasing 1B SG Loop Tave =578 of slowly decreasing Tave Setpoint = 579 of Based on the above conditions, which ONE of the following states the validity of the SG Low Level Limit Stat Alarms?

A. ONLY 1A SG Stat Alarm is valid B. ONLY 1B SG Stat Alarm is valid C. BOTH 1A and 1B SG Stat Alarms are valid D. Neither 1A and 1B SG Stat Alarms are valid

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 63 Unit 3 initial conditions:

Time =0400 Reactor power =25%

EHC DISCHARGE HEADER PRESSURE =1600 psig TURBINE BEARING OIL PRESSURE =22 psig decreasing Current conditions:

Time =0401 EHC DISCHARGE HEADER PRESSURE =1200 psig TURBINE BEARING OIL PRESSURE = 7 psig increasing Based on the current conditions, which ONE describes the response of the Main Turbine and the RPS system?

The Main Turbine will trip due to low...

A. EHC DISCHARGE HEADER PRESSURE and RPS will trip the reactor.

B. EHC DISCHARGE HEADER PRESSURE and RPS will NOT trip the reactor.

C. TURBINE BEARING OIL PRESSURE and RPS will trip the reactor.

D. TURBINE BEARING OIL PRESSURE and RPS will NOT trip the reactor.

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 64 Initial plant conditions:

All units 100 power Unit 1 Gaseous Waste Release (GWR) is planned 1RIA-37 is inoperable due to a failed source check 1RIA-37 background is 1.3 e+03 cpm 1RIA-38 background is 1.0 e+01 cpm Current plant conditions:

GWD Tank Sample Request recommends resetting RIA's as follows:

~

1RIA-37 at 800 cpm above background

~

1RIA-38 at 30 cpm above background Based on the above conditions, which ONE of the following describes the correct setpoints used for 1RIA 37 & 1RIA-38?

A. 1RIA-37 is set to 2.1 e+03, 1RIA-38 is set to 4.0 e+01 B. 1RIA-37 is set to 0.0, 1RIA-38 is set to 4.0 e+01 C. 1RIA-37 is set to 2.1 e+03, 1RIA-38 is set to 3.0 e+01 D. 1RIA-37 is set to 0.0, 1RIA-38 is set to 3.0 e+01

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 65 Unit 1 plant conditions:

1SA3/B6 (FIRE ALARM) actuated Based on the above conditions, which ONE of the following describes the status of the Fire Alarm Control Panel and 1SA3/B6 Stat Alarm?

A. Only ONE alarm location can be displayed until the initial alarm is cleared and reset.

1SA3/B6 can alarm again as soon the existing Fire Alarm Control Panel alarm(s) are acknowledged.

B. Multiple alarms can be displayed using the Prev/Next Switch to scroll before any alarms are reset.

1SA3/B6 can not alarm again until the condition has cleared and current Fire Alarm Control Panel Alarm is reset.

C. Only ONE alarm location can be displayed until the initial alarm is cleared and reset.

1SA3/B6 can not alarm again until the condition has cleared and current Fire Alarm Control Panel Alarm is reset.

D. Multiple alarms can be displayed using the Prev/Next Switch to scroll before any alarms are reset.

1SA3/B6 can alarm again as soon the existing Fire Control Panel alarm(s) are acknowledged.

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 66 Unit 1 plant conditions:

MODE 6 Reactor shutdown 5 days ago Defueling in progress 1RIA-3 (Fuel Transfer Canal Monitor) has been declared out of service Repair expected to take 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Fuel handling was suspended in the Reactor Building when 1RIA-3 failed Based on the above conditions, which ONE of the following describes the status of fuel handling operations in the Reactor Building?

A. Fuel handling activities can resume as long as the Main Fuel Bridge Area Monitor remains operable.

B. Fuel handling activities can resume as long as 1RIA-49 (RB Vent Gas) remains operable.

C. Fuel handling activities cannot be resumed until 1RIA-3 is declared operable.

D. Fuel handling activities can resume using a portable instrument that has the appropriate range and sensitivity.

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 67 An ECP is calculated for Unit 1 at the following conditions:

400 EFPD 535 of RCS Temperature 200 ppmB RCS boron concentration

(-1.47%) L1k/k Xenon/Samarium Concentration The Estimated Critical Position is calculated to be CRD Group 7 at 30%

wId Which ONE of the following changes will result in an Estimated Critical Position of CRD Group 7 greater than 30%

wId?

A. 395 EFPD B. 537°F RCS temperature C. (-1.260/0) L1k/k Xenon/Samarium Concentration D. 190 ppmB RCS boron concentration

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 68 Unit 1 and 3 Conditions:.

Mode 4 RCS Cooldown in Progress LPI in-service RCP's secured Which ONE of the following correctly describes the actions directed by procedures to reduce the cooldown rate of the RCS on each of the Units?

A.

Unit 1 - Raise LPI Flow through the LPI Cooler Bypass Line while reducing LPI Flow through the cooler Unit 3 - Lower LPSW Flow through the in-service LPI Cooler B.

Unit 1 - Lower LPSW Flow through the in-service LPI Cooler Unit 3 - Raise LPI Flow through the LPI Cooler Bypass Line while reducing LPI Flow through the cooler C.

Unit 1 - Lower LPI Flow through the LPI Cooler Bypass Line while raising LPI Flow through the cooler Unit 3 - Raise LPSW Flow through the in-service LPI Cooler D.

Unit 1 - Raise LPSW Flow through the in-service LPI Cooler Unit 3 - Lower LPI Flow through the LPI Cooler Bypass Line while raising LPI Flow through the cooler

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 69 Unit 1 plant conditions:

EFDWP Discharge Startup Checklist in progress 1C-156 (TO EFDWP Normal Supply) checklist position is OPEN 1C-156 (TO EFDWP Normal Supply) is Red Tagged CLOSED per an R&R to repair a packing leak Based on the above conditions, which ONE of the following describes the process for closing the valve checklist (if any)?

A. Review the impact of the out of position valve, list the R&R number on the checklist and initial B. Review the impact of the out of position valve, list the Work Request number on the checklist and initial C. Review the impact of the out of position valve, N/A the block and note on the checklist that an R&R is outstanding and initial D. The valve checklist cannot be closed with a valve out of position

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 70 Unit 1 plant conditions:

MODE 3 SR 3.1.1.1 (Verify SDM is within the limit specified in the COLR) has a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> frequency SR 3.1.1.1 was last performed at 1000 on 8/12 Based on the above conditions and applying any extensions allowed, which ONE of the following indicates the latest time that SR 3.1.1.1 must be performed before it is classified as a missed surveillance?

A. 8/13 @ 1000 B. 8/13 @ 1600 C. 8/13 @ 1900 D. 8/14 @ 1600

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 71 A NEO is to valve out the Unit 1A Seal Supply filter.

Based on the RWP and the Plan View, which ONE of the following describes the maximum time (minutes) he can take to perform this task before he must exit the area?

SEE ATTACHMENT A.33 B. 60 C. 166 0.300

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 72 Plant conditions:

Refueling of Unit 3 is complete The Reactor Vessel Head is installed RCS temperature is being maintained at 150 of An NEO must enter the Reactor Annulus Which ONE of the choices fills in the blanks of the following statement?

Access to the Reactor Annulus is controlled by

. The in-core wires must be

_____ before entry is permitted, and RP coverage is required for entry.

A. RP Supervisor / Manager; "parked"; periodic B. RP Supervisor / Manager; fully inserted into the reactor core; continuous C. Operations Shift Manager; "parked"; continuous D. Operations Shift Manager; fully inserted into the reactor core; periodic

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 73 Unit 3 plant conditions:

Reactor power = 100%

3A and 3B RCW pumps tripped Based on above conditions, which ONE of the following states the procedure that should be entered?

A. EP/3/A/1800/001 (Emergency Operating Procedure)

B. AP/3/A/1700/22 (Loss of Instrument Air)

C. AP/3/A/1700/29 (Rapid Unit Shutdown)

D. AP/3/A/1700/35 (Loss of SFP Cooling and/or Level)

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 74 Unit 1 initial conditions:

Reactor power = 100%

Current conditions:

Switchyard isolation due to low switchyard voltage CT1 lockout Based on the above conditions, which ONE of the following states what will initiate the trip and which operator will be directed to perform AP/25 (Standby Shutdown Facility Emergency Operating Procedure)?

A. Loss of MFWPs / BOP B. Loss of MFWPs / OATC C. High RCS Press / BOP D. High RCS Press / OATC

OCONEE NRC RO EXAM 03-20-2008 1 POINT Question 75 Unit 1 plant conditions:

Reactor power = 100%

1RIA-40, CSAE Off-Gas Monitor, reading is rising slowly 1RIA-54, Turbine Building (TB) Sump Monitor, is inoperable The operating crew has just entered AP/31, PRIMARY TO SECONDARY LEAKAGE Based on the above conditions, which ONE of the following describes who must be notified and a required action?

The operating crew must notify to sample the TB sump and direct an NEO to A. Secondary Chemistry / open and white tag the TB Sump Pump breakers.

B. Secondary Chemistry / align the TB Sump to the TB Sump Monitor Tanks.

c. Radiation Protection / open and white tag the TB Sump Pump breakers.

D. Radiation Protection / align the TB Sump to the TB Sump Monitor Tanks.